ML20112B347

Affidavit of Kw Cook Supporting Conclusion That Cracks Do Not Significantly Affect Structural Adequacy of Facility Basemat.Related Correspondence

ML20112B347
Person / Time
Site:	Waterford
Issue date:	01/03/1985
From:	Cook K LOUISIANA POWER & LIGHT CO.
To:
Shared Package
ML20112B305	List: ML20112B302 ML20112B329 ML20112B341 ML20112B347 ML20112B358
References
OL, NUDOCS 8501100334
Download: ML20112B347 (7)

Text

f to Ek gu;=~ January 3, 1985 3 , , ,q UNITED STATES OF AMERICA -

NUCLEAR REGULATORY COMMISSION 64 3

Before the Atomic Safety and Licensing AppdalvBoard w

In the Matter of ) --

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LOUISIANA POWER & LIGHT COMPANY ) Docket No.'50-382 OL

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(Waterford Stg m Electric Station, ) CCCHE ' '3 EFT LCSM Unit 3) w )

AFFIDAVIT OF KENNETH W. COOK The undersigned, being duly sworn, deposes and says:

My name is Kenneth W. Cook. My address is 142 Delorande Street, New Orleans, Louisiana 70174. I am Nuclear Support &

Licensing Manager for Louisiana Power & Light Company. In this position I am responsible for licensing activities for Waterford 3, interfacing with state and federal regulatory agencies and_for providing technical support for the plant staff in the areas of Radiation Control, Nuclear Engineering, Fuels Management, Chemistry and Radiochemistry.- A copy of my pro-fessional qualifications is attached.

Cracks in the basemat were-discovered in 1977 which ran generally along the East-West centerline of the basemat in the area now under the Reactor Containment Building _(RCB). Subse-quent to May 1983, additional cracks running generally along the East-West centerline in the open areas, outside of the containment building, were discovered. These cracks, as well as the 1977 cracks, became the subject of extensive evaluation 8501100334 B50107 PDR ADOCK 05000382 9_ PDR c

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• 4 by LP&L and the NRC Staff. LP&L's view, as expressed to the NRC Staff, was_that the cracks discovered in 1977 (within the RCB) and the cracks discovered in-19R3 (outside the RCB) were all formed prior to 1977 during placement of the basemat from a combination of flexure and thermal effects. Brookhaven National Laboratory (BNL) stated at page 11 in its July 18, 1984 Report, which was submitted to the Appeal Board by the NRC Staff on July 25, 1984, that the cracks "would be expected to have occurred after construction of the superstructure, but before placement of the backfill." BNL has since revised its opinion and now believes the cracks to have occurred even earlier. (BNL Report, Addendum 2, page 3, December-14, 1984).

In any event, the Appeal Board, assuming that the backfill was placed prior to 1983 (backfill placement was essentially

,- completed in 1977-78), asked the NRC Staff, at pages 11-12 of ALAB-786, October 2, 1984, why the 1983 cracks were not dis-covered sooner.

In a letter dated October 19, 1984 from Dennis M. Crutchfield,

-Assistant Director for Safety Assessment (USNRC) to Mr. J. M.

- Cain, President and Chief Executive Of ficer (LP&L) , Louisiana Power & Light was asked to ruspond to several questions regarding the Waterford 3 basemat.' One of these questions stated "On l page 12'of the Appeal Board's Memorandum and Order it is asked-why the cracks in the basemat were not discovered before May 1983.

Please provide the staff with your explanation of why this was so." I was asked to provide a response to this letter and documented the response via letter W3P84-3044 from K. W. Cook,

(

2 Nuclear Support & Licensing Manager (LP&L) to Dennis M. Crutchfield, Assistant Director for Safety Assessment (USNRC), dated October 26, 1984.

My sense of the question from the Appeal Board and the NRC Staff was that, if the cracks outside the RCB has existed since before 1977, why had they not been discovered until 1983. The ,

cracks of interest were considered to be those cracks running generally along the East-West centerline in the open areas in the vicinity of the RCB which had been the focus of analytical and nondestructive testing investigations by the NRC Staff, LP&L and their consultants. The answer is as stated in my October 26, 1984 letter:

"The reference letter requested a statement on why the cracks in the basemat were not discovered prior to May -

1983. The cracks observed in 1977 were noted as a result of preparing the containment area for pouring fill con-crete. The engineering evaluation of these cracks deter-mined they were of no structural significance but should be repaired to ensure a good bond between the fill con-crete and the basemat. The areas-of the basemat adjacent to the containment area continued to be congested with materials and water laying on the basemat'from the ongoing construction activities in these areas. Since the cracks in the containment area were dispositioned as being not significant and'no fill material was to be placed in areas outside the containment area, no effort was made to clean up or dry out the basemat to determine if ' additional cracks existed. The construction activities continued in these areas until late 1982 and early 1983 when final clean up of the areas was begun. In May 1983, during the clean up activities, the cracks in the reactor auxiliary building were observed. As a result of the review undertaken by LP&L, the basemat for the containment annulus, fuel handling building and reactor auxiliary building were mapped for cracks."

I s/ KENNETH W. COOK e

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' Subscribed and sworn to before me this 3rd day of January, 1985.

' NOTARY PUBLIC

.My Commission Expires: M-30-IC U

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L= 1 0 Resume of  !

KENNETH W. COOK EDUCATIONAL BACKGROUND e University of Wyoming B.S. in Mechanical Engineering (with honors) -

Nuclear Option (1960-1964) e University of California. Berkeley M.S. in Mechanical Engineering (1967-1968) e General Electric Advanced Engineering Courses (1965-1968) e Numerous General Electric Sponsored Management &

Engineering Courses & Seminars PROFESSIONAL LICENSE Registered Professional Nuclear Engineer - California PROFESSIONAL LEVEL EXPERIENCE LOUISIANA POWER & LIGHT COMPANY -

(1983 - Present)

Nuclear Support & Licensing Manager (9/83 - Present)

Responsible for managing the LP&L Nuclear Licensing and Nuclear Support organizations which are responsible for licensing activities for Waterford 3, interfacing with state and federal regulatory agencies and for providing technical support to the plant staff in the areas of Radiation Control.

Nuclear Engineering, Fuels Management. Chemistry and Radiochemistry.

WASHINGTON PUBLIC POWER SUPPLY SYSTEM (1980 - 1983)

Licensing Project Manager (4/80 - 9/83)

Licensirg Manager for two nuclear power plants (one plant terminated in 1982);

responsible for obtaining operating license and resolution of licensing issues with the NRC. Direct efforts of Architect / Engineer. Nuclear Steam Supply System (NSSS) vendor Project Technical staf f, Operations staf f and outside consulting agencies in preparing submittals to NRC and other regulatory agencies. Develop licensing strategies, schedules, resource commitments and manage implementation of programs through licensing department staf f.

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GENERAL ELECTRIC COMPANY (1964 - 1980)

-Senior Licensina Engineer (6/79 - 3/80)

Program Manager for resolution of 11 censing issues associated with twenty-two (22) operating Boiling Water Reacters (BWR's). Responsibilities included development of licensing action plans, coordination of technical resolution

.and resolution of issues with NRC.

Senior' Licensing Engineer -(5/77.- 5/79)

Program manager for generic licensing issues involving transient analyses for GE Boiling Water Reactors (BWR's). Programs included licensing of one-dimensional transient analysis model including development of licensing action plans, establishment of licensing basis, coordination of review with NRC and negotiation of licensing basis..

Senior Engineer (6/75 - 5/77)

Clinch River Breeder Reacto* Project (CRBRP) cognizant engineer and program manager for safety of intermediate Heat Transport System (IHTS), Steam Generator Auxiliary Heat Removal System (SGAHRS), large sodium pumps and several analytical.

tasks including sodium fire, radiological and core disassembly analyses.

Enaineer 1 (12/71 - 6/75)

Established safety design guidelines and performed safety conformance reviews for GE scope of supply on CRBRP. Coordinated GE input to CRBRP PSAR.

Directed safety analysis tasks relating to CRBRP Primary and Intermediate Systems sodium fires and structural evaluation of reactor vessel and internals during a core disassembly accident.

. Performed studies of Radioactive Waste Management System and Containment System requirements, Refueling Accident Analysis Study, Refueling System Plow Chart

.and Safety Assurance Diagrams for the GE Demonstration Plant design.

Directed adaptation of Argonne National Laboratory developed REXCO computer code for use-in GE evaluations of Hypothetical Core Disassembly Accident (HCDA),

effects on the reactor internals and reactor vessel. Updated national LMFBR Program Plan in areas of Safety and Control Rod Assemblies.

Engineer 1 (1/73 - 9/73) Special Assignment Provided consultation and performance of analytical tasks relating to new conce; +

in Boiling Water Reactor contairunant design.

d 0

l Enmineer II (3/68 - 12/71) i Performed transient neutronic and thermal-hydraulic analyses in support of the SEFOR follow-on program and developed Design Safety Criteris for usage in the program. Developed an outline of Technical Specifications for the Demo Plant PSAR. Initiated and directed analysis of pipe break accidents within the primary system for the Demo Plant.

Developed a computer model for evaluation of the detailed fluid velocity distribution for interior and corner fuel pins in an LMFBR fuel bundle.

Engineer (10/67 - 3/68)

- Attending University of California at br rkeley as par of GE Advanced Engineering Course to obtain Masters Degree.

Ensineer (6/64 - 10/67)

Developed detailed design, test plans and test operation plans for LMFBR fuel assembly water flow tests. Developed LMFBR test requirements for core fuel assembly thermal-hydraulics. Developed criteria and analytical models for evaluation of LMFBR fuel pin spacer assemblies.

Performed core thermal-hydraulic evaluations and prepared fuel test specifications for Superheat Reactor test fuel under irradiation at the EVESR superheat reactor test facility.

Prepared Core Design and Plant Data Sheets for Boiling Water Reactor (BWR) proposals.

Developed experimental plans and designed test facilities and test section for BWR spacer pressure drops and feasibility study for UNISEAL for Superheat Reactor applications.

Reviewed design of BWR control rod drives and modified design to reduce cost of annufacture. Developed detailed cost breakdown of drive manufacturing process.

PHILLIPS PETROLEUM COMPANY (1963)

Nuclear Engineer (6/63 - 9/63)

Participated in fuel Development Program for the Advanced Test Reactor. Set up corrosion test loop and monitored fuel test specimens.

- I